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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Y. Nanjou, K. Tatenuma, S. Ueda, M. Matsuyama, T. Itoh, K. Watanabe
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1151-1154
Isotope Separation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22764
Articles are hosted by Taylor and Francis Online.
In order to improve the efficiency in gas chromatographic isotope separation technology, porous SiC supporting palladium-platinum (Pd-Pt) alloy as a column material was developed. It was confirmed that the utilization of the column material developed enabled higher recovery yield of 90 % and the higher purity of 97 % for deuterium isotopic separation comparing with the method using conventional column materials such as the mixture of Pd-Pt alloy filler under 100 mesh and Cu powder from 40 to 80 mesh.
